Effects of molybdenum on microstructural evolution and mechanical properties in Zr-Nb alloys as nuclear fuel cladding materials

Hui Long Yang, Hiroaki Abe, Sho Kano, Yoshitaka Matsukawa, Yuhki Satoh

Research output: Contribution to journalArticlepeer-review

3 Citations (Scopus)

Abstract

The Zr-Nb alloys were modified by doping of Mo as a minor alloying element to seek for the nuclear fuel cladding materials with better characteristics. The effects of Mo on microstructural evolution and mechanical properties in Zr-Nb alloys were systematically investigated and elucidated. Results showed that the martensitic microstructure, a mixture of lath martensites and lens martensites with internal twins, was observed in the alloys quenched from β-phase. Width of the lath martensite reduced with the increasing Mo concentration, and the volume fraction of lens martensite increased with increase in the Mo concentration. After final annealing, a new kind of precipitate, namely β-(Nb, Mo, Zr), was identified in the Mo-containing alloys. It was also found that Mo reduced the growth of the precipitates but increased their number density. Furthermore, Mo addition retarded the recrystallization process strongly and reduced the grain size significantly. In terms of the mechanical properties, Mo addition enhanced the yield strength and the ultimate tensile strength at room temperature, however decreased the ductility. The grain size strengthening was presumed as the greatest contributor in this system.

Original languageEnglish
Pages (from-to)1265-1273
Number of pages9
Journaljournal of nuclear science and technology
Volume52
Issue number10
DOIs
Publication statusPublished - 2015 Oct 3

Keywords

  • Mo addition
  • fuel cladding
  • mechanical property
  • microstructure
  • recrystallization
  • zirconium alloy

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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